ML17332A286

Forwards DC Cook Nuclear Plant Simulation Facility for Yr Rept,Per 10CFR55.45(b)(5)(ii).Form NRC-474 for Facilities Also Encl for Convenience

ML17332A286
Person / Time
Site:	Cook
Issue date:	08/31/1994
From:	Fitzpatrick E INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	Russell W NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
AEP:NRC:1134A, NUDOCS 9409090022
Download: ML17332A286 (40)

Text

P R.I @3 H.IMW h,CCELERATED RIDS PROCESSING) 1 REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9409090022 DOC.DATE: 94/08/31 NOTARIZED: NO DOCKET FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana M 05000315 50-316 Donald C. Cook Nuclear Power Plant, Unit 2, Indiana M 05000316 AUTH. NAME AUTHOR AFFILIATION P FITZPATRICK,E. Indiana Michigan Power Co. (formerly Indiana & Michigan Ele .

RECIP.NAME RECIPIENT AFFILIATION RUSSELL,W.T. Document Control Branch (Document Control Desk) R

SUBJECT:

Forwards Donald C Cook Nuclear Plant Simulation Facility Four Year Rept.

DISTRIBUTION CODE: A005D COPIES RECEIVED:LTR t ENCL ( SIZE: 0 TITLE: Simulator Facility Certification GL-90-08 NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL HICKMAN,J 1 1 INTERNAL.~CENTRAL FILE 0 i 1 1 NRR/DRCH/HOLB 1 1 EXTERNAL: NRC PDR 1 1 D

0 C

N NOTE TO ALL"RIDS'ECIPIENTS:

PLEASE HELP US TO REDUCE iVASTE! CONTACT TI.IE DOCUMENT COi iTROL DESK, ROOM P!-37 (EXT. 504-2083 ) TO ELIMfiNATEYOUR NAME FROM DISTRIBUTION LIS'rs r'OR DOCUMEi 4TS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 4 ENCL 4

Indiana Michigan Power Company s, ' P.O. Box 16631 Columbus, OH 43216 AEP:NRC'1134A Donald C. Cook Nuclear Plant Units 1 and 2 Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 DONALD C. COOK NUCLEAR PLANT SIMULATION FACILITY FOUR YEAR REPORT U. S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Attn: W. T. Russell August 31, 1994

Dear Mr. Russell:

In 'accordance with 10CFR55.45, (b)(5)(ii), Indiana Michigan Power Company hereby submits the Cook Nuclear Plant Simulation Facility four year report. The attached report encompasses both Cook Nuclear Plant Unit 1 (50-315) and Cook Nuclear Plant Unit 2 (50-316). Additionally, although not required by 10CFR55.45, included for your convenience is Form NRC-474 for both units.

Sincerely, E. E. Fitzpatrick Vice President Attachment ar cc: A. A. Blind Frank Collins - NRR/LPEB G. Charnoff J. B. Martin - Region II NFEM Section Chief NRC Resident Inspector - Bridgman J. R. Padgett ml~ Il A q409090022 ~408>~

PDR 'ADOCK 05000315 PDR

ATTACHMENT TO AEP:NRC:113'ONALD C. COOK NUCLEAR PLANT SIMULATION PACXLITY POUR YEAR REPORT

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Attachment to AEP:NRC:1134A Page 2 DONALD C. COOK NUCLEAR PLANT SIMULATOR FOUR YEAR REPORT UNIT ONE A. Purpose The Cook Nuclear Plant simulator is used in the licensing of operations personnel and is therefore required to meet the criteria established in 10 CFR 55 Subpart E, Section 55.45.

To comply with 10 CFR 55.45, a report to the Commission which identifies simulator testing status must be submitted by the fourth anniversary of original certification. The purpose of this report is to satisfy this reporting requirement for- Cook Nuclear Plant simulator.

This report addresses the use of Cook Nuclear Plant simulator for training on Cook Nuclear Plant Unit 1.

B. References Title 10, Code of Federal regulations, Part 55, 'Operator Licenses', Subpart E, Section 45.

2. U. S. Nuclear Regulatory Guide 1.149 'Nuclear Power Plant Simulation Facilities for use in Operator License Examinations.

3. ANSI 3.5, 1985, 'Nuclear Power Plant Simulators for use in Operator Training.

C. Reporting Requirements The requirements of this report as outlined in 10 CFR 55 are:

Identification of any uncorrected performance test failures and a schedule for correction of such performance failures, if any. Subpart E, Section 55,45 (b)(5)(ii).

2. A description of performance testing completed for the simulation facility. Subpart E, Section 55.45 (b) (5) (vi).

Attachment to AEP:NRC:1134A Page 3

3. A description of the performance tests, if different, to be conducted on the simulation facility during the subsequent four year period. Subpart E, Section 55.45 (b)(5)(vi).

4. A schedule for .the conduct of approximately 25 percent of the performance tests per year for the subsequent four-years.

Subpart E, Section 55.45 (b)(5)(vi).

D. Discussion The Cook Nuclear Plant simulator functions to provide training for both Units of the Cook Nuclear Plant. Unit 2 four-year report is also provided herein. The simulator is modelled to Cook Nuclear Plant Unit 2.

The initial certification report provided a demonstration that the differences between the units were not so significant that they impacted the ability of the simulation facility to meet the requirements and guidance of ANSI/ANS-3.5 1985 per NRC Regulatory Guide 1.149 'he simulator was certified as acceptable for training on both units based upon this study and a commitment made to maintain a Unit 1 'raining load' The Unit 1 'raining load',

although developed, has not been used for training during the course of the four-year period from initial certification to present.

Training commitments for simulator usage, simulator equipment limitations, and simulator staffing limitations preclude maintaining a Unit 1 "training load". Based upon the following rationale, Plant proposes to no longer maintain a Unit 1 " trainingCook'uclear load" .

An evaluation was performed on the Unit 1 specific plant modifications installed in Unit 1 from January 1, 1990, to present, to determine the impact of those changes upon the original certification differences study. This evaluation determined that as a result of a change to Unit 1 "control room, training on Cook Nuclear Plant Unit 2 simulator would not be likely to result in an operator error resulting in a challenge to a critical safety function in Unit 1. Design changes specific to Unit 1 will be reviewed to ensure no differences exist between the simulator and Unit 1 that,.would affect the ability for safe operation of Unit 1.

2. A review was performed of all Unit 1 plant condition reports with training qualification methods/content causal codes with operations identified as the involved department. This review identified no cases in which training on the Unit 2 simulator resulted in an error in operation of Unit 1.

Attachment to AEP:NRC:1134A Page 4

3. Both units use Westinghouse Owners Croup based emergency operating procedures (EOPs) and in September 1993 both unit' abnormal operating procedures (AOPs) were standardized to the EOP two column format. Except for some set point differences between units, these procedures are virtually identical between units. Extensive training was performed on the simulator in the use of the new AOPs.

4. During the four-year period from initial certification to present, Unit 1 had fewer reactor trips than Unit 2 (two trips on Unit 1 vs nine on Unit 2). A review of trip causes showed no operator error induced trips on Unit 1 and only one on Unit 2 in which operator action was contributory. This data shows that not performing Unit 1 specific simulator training had no significant impact on normal operating performance.

5. During the four-year period from initial certification to present, Unit 1 set a plant operating continuous run record of 470 days.

6. Where design changes affect both units, installation on the simulator is completed prior to installation in either Cook Nuclear Plant unit when training could be enhanced and overall plant operation improved. An example of this philosophy is that a major modification consisting of replacement of Foxboro H Line equipment with Taylor Mod 30 controllers was performed during the 1994 Unit 1 refueling outage. This modification was installed on the simulator in October 1993, training was conducted on the simulator. relative to the new controllers, and an essentially error free startup was conducted on Unit 1 at the completion of the outage. This modification is scheduled for Unit 2 in September 1994.

E. Implementation Requirement ¹1: Uncorrected performance tests failures and a schedule for correction of such performance failures.

Refer to Cook Nuclear Plant Simulator Four Year Report Unit 2 for a list of performance test failures and scheduled correction dates.

Attachment to AEP:NRC:1134A Page 5 Requirement ¹2: Description of performance testing performed in the last four-year period.

No performance testing was performed specific to the Unit 1 "training load" during the last four year period. Performance testing of the simulator was performed in accordance with t'e testing schedule per the original certification submittal on Unit 2 "training load". Refer to Cook Nuclear Plant Simulator Four-Year Report Unit 2 for performance testing abstract and completion dates.

Requirement ¹3: Description of performance tests, if different, to be conducted on the simulation facility during the subsequent four year period.

Refer to Cook Nuclear Plant Simulator Four Year-Report Unit 2, (pages 26 thru 34) for a complete list of certification tests to be performed on the simulator in the next four-year period.

New tests added to the simulator include:

CC10: CCW Inleakage to RCP Lower Bearing Oil Reservoir RC12: RCP Lower Bearing Oil Reservoir Leak RC29: Steam Generator Blowdown Leak Upstream of Containment Isolation Vlv RM03 Eberline Radiation Monitor Failures RP21: Failure of Feedwater Isolation to Occur RX29: Feedpump Discharge Pressure Transmitter (FPC-250)

Failure TRANSIENT ll: Load Rejection Requirement ¹4: Schedule for the conduct of approximately 25 percent of the performance tests per year for the subsequent four years.

No performance testing will be performed specific to a Unit 1 "training load" per "D. Discussion" above. Refer to Cook Nuclear Plant Simulator Four-Year Report Unit 2 , (pages 26 thru 34) for the schedule of certification testing to be performed over the next four-year period on the Unit 2 "training load". Approximately 25% of all malfunction testing is scheduled annually.

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Attachment to AEP:NRC:1134A Page 7 DONALD C. COOK NUCLEAR PLANT SIMULATOR FOUR- YEAR REPORT UNIT TWO A. Purpose The Cook Nuclear Plant simulator is used in the licensing of operations personnel and is therefore required to meet the criteria established in 10 CFR 50.55 Subpart E, Section 55.45.

To comply with 10 CFR 55.45, a report to the Commission which identifies simulator testing status must be submitted by the fourth anniversary of original certification. The purpose of this report is to satisfy this reporting requirement for the Cook Nuclear Plant simulator.

B. References Title 10, Code of Federal regulations, Part 55, 'Operator Licenses', Subpart E, Section 45.

2. U. S. Nuclear Regulatory Guide 1.149 'Nuclear Power Plant Simulation Facilities for use in Operator License Examinations.

3. ANSI 3.5, 1985, 'Nuclear Power Plant Simulators for use in Operator Training.

C. Reporting Requirements The requirements of this report as outlined in 10 CFR 50.55 are:

Identification of any uncorrected performance test failures and a schedule for correction of such performance failures, if any. Subpart E, Section 55.45 (b)(5)(ii).

2. A description of performance testing completed for the simulation facility. Subpart E, Section 55.45 (b)(5)(vi).

Attachment to AEP:NRC:1134A Page 8

3. A description of the performance tests, conducted if different, to be on the simulation facility during the subsequent four-year period. Subpart E, Section 55.45 (b)(5)(vi).

4. A schedule for the conduct of approximately 25 percent of the performance tests per year for the subsequent four years.

Subpart E, Section 55.45 (b)(5)(vi).

D. Implementation Requirement ¹1: Uncorrected performance tests failures and a schedule for correction of such performance failures.

Uncorrected performance test failures include:

DR 93413 and 94068: Slight Tave increase following reactor trip. This increase is extremely short in duration and has very little training impact.

DR 94074: Pressurizer surge line temperature response is too rapid with pressurizer insurge and outsurge conditions.

DR 94078: Identify reason for and correct as necessary containment pressure spikes during large break LOCA.

DR 94066: Main generator seal oil response is incorrect when a seal oil leak is inserted.

DR 94128: Condenser Delta T values do not match plant information at low power.

DR 94214: Auxiliary feed line leak would not isolate properly.

A DR 94252: Reactor head leak is collected in the wrong containment sump.

These DR' are scheduled for completion within one year of origination dates.

DR 93413 Completion date: 11/08/94 DR 94068 Completion date: 01/24/95 DR 94074 Completion date: 01/27/95 DR 94078 Completion date: 01/31/95 DR 94066 Completion date: 01/22/95 DR 94128 Completion date: 03/31/95 DR 94214 Completion date: 06/04/95 DR 94252 Completion date: 08/13/95

Attachment to AEP:NRC:1134A Page 9 Requirement 82: Description of performance testing performed in the last four-year period.

ANSI 3.5, 1985 Appendix A lists the requirements relative to certification testing for nuclear plant simulators. These requirements fall into four separate categories.

Computer Real Time Test-verification of real time simulation by the simulator.

2. Steady State and Normal Plant Evolution Performance Tests a) Steady State Tests-verification of simulator stability and verification that process parameter values reflect actual reference plant values.

b) Normal Plant Evolutions Performance Tests-verification of simulator ability to perform in accordance with reference plant operating procedures.

3. Transient tests-verification of simulator' ability to reproduce defined transients Malfunction testing-testing of each generic malfunction to verify simulator response and system interaction.

Computer Real Time Test.

ANSI 3.5, 1985 requires real time verification to ensure the simulation dynamic performance is in the same time base relationships, sequences, durations, rates and accelerations as the dynamic performance of the reference plant.

The Cook Nuclear Plant simulator uses Real Time Executive Tasks (RTEX) to ensure that the simulator remains in real time during all simulation. This task uses a frame counter routine to ensure an overtime abort and'imulator 'reeze'ondition occurs if the Real Time Executive Task fails to execute in allotted time period.

Simulator real-time tests have been performed annually with no failures identified. See pages 12 thru 25 for test performance dates.

Attachment to AEP:NRC:1134A Page 10 Steady State and Normal Plant Evolutions Testing.

To ensure compliance with the standard regarding simulator steady state operation, the simulator has been operated at one hour intervals without operator action at power levels of 30%,

60%, 90%, and 100% as per the original certification testing schedule. Computed values were collected at half second intervals over the one hour time period for each power level.

This data has been verified accurate against actual plant data and heat balance information to be within the tolerances for critical and non-critical parameters as established in ANSI 3.5, 1985. This data has also been plotted and verified not to vary more than 2% from initial values.

Refer to page 16 for steady state test abstract and completion dates.

Normal plant evolutions are tested and verified against the criteria established in ANSI 3.5 Section 3.1.1 annually per original certification schedule. These tests are performed in accordance with approved plant procedures as listed on page 15.

In addition to testing performed by simulator personnel, these evolutions have been tested as an integral step of the Reactor Operation Replacement training program. This program involves continuous operation (per approved plant procedures) of the simulator from full power to half loop conditions, and from half loop back to full power operation by instructors and SRO candidates with numerous years of plant operating experience.

ANSI 3.5 tests not listed or performed on a regular schedule are clarified below.

Core performance testing (3.1.1.9) is performed on the simulator when core cycle upgrades are made on the simulator (same cycle as the reference plant).

Operations surveillance tests (3.1.1.10) are performed on an as needed basis within the operations training program using approved plant procedures.

Transient Testing.

All transient tests required by ANSI 3.5, Appendix B section B.2.2 have been conducted on the simulator per the original certification schedule.

Attachment to AEP:NRC:1134A Page 11 The data collected in the performance of these tests is collected at one half second intervals and has been compared to actual data where existing data was available.

These tests have been reviewed by a team of subject matter experts made up of operations and simulator personnel.

Refer to pages 17 and 18 for transient test abstracts and completion dates.

Malfunction Testing.

The Cook Nuclear Plant simulator has 310 malfunctions used to introduce transients and/or faults into the simulator for operator training. All malfunctions have been tested in the previous four year period with approximately 258 tested annually.

Refer to pages 19 thru 25 for malfunction test abstracts and completion dates.

Requirement ¹3: Description of performance tests, if different, to be conducted on the simulation facility during the subsequent four year period.

Refer to pages 26 thru 34 for a complete list of certification tests to be performed on the simulator in the next four year period. New tests added to the simulator include:

CC10: CCW Inleakage to RCP Lower Bearing Oil Reservoir RC12: RCP Lower Bearing Oil Reservoir Leak RC29: Steam Generator Blowdown Leak Upstream of Containment Isolation Vlv RM03: Eberline Radiation Monitor Failures RP21: Failure of Feedwater Isolation to Occur RX29: Feedpump Discharge Pressure Transmitter (FPC-250)

Failure TRANSIENT 11: Load Rejection Requirement ¹4: Schedule for the conduct of approximately 25 percent of the performance tests per year for the subsequent four years.

Pages 26 thru 34 outline the schedule for certification testing to be performed over the next four year period. Approximately 25% of all malfunction testing is scheduled annually.

Attachment to AEP:NRC:1134A Page 12 DONALD C. COOK NUCLEAR PLANT SIMULATOR CERTIFICATION TESTING The following pages consist of testing information relative to'he Cook Nuclear Plant simulator certification requirements. The sections are:

Computer Real Time testing Normal Plant Evolution (NPE) testing Steady State Testing Transient Testing Malfunction testing All testing has been completed per requirements of ANSI 3.5, 1985 as amended by Regulatory Guide 1.149.

Deviations from test schedule submitted in the original certification report follow.

Special Transient Test ST-3 scheduled for completion in third quarter of 1991 was not completed or all data pertaining to the test was lost. Test was not identified as being delinquent until it became due in the third quarter of 1992. This is an in-house test and not a requirement of ANSI 3.5 appendix A.

Special Transient Tests ST-1 and ST-2 and Steady State Test SS-Ol scheduled for completion in the first and second quarters of 1991 were not completed until the fourth quarter of same year. Review of yearly test'ompletion identified incomplete tests and they were immediately rescheduled.

Special Transient Tests ST-4 scheduled for completion in the fourth quarter of 1992 was not completed until January 15, 1993. Test data review identified plant data corresponded to 90%. thermal power, original test performed as scheduled was run at 100$

power. Test was immediately rescheduled and completed at the proper power level.

Malfunction Tests ED12, ZA04, RH07, TC12, RMOl scheduled for completion in the first and second quarters of 1991 were completed in the fourth quarter of 1991. Test review identified no documentation of these tests as being performed and they were immediately rescheduled.

Attachment to AEP:NRC:1134A Page 13 Malfunction test RP12 was not performed in the fourth quarter of 1990. Test was inadvertently scheduled for both the third and fourth quarters of 1990. Test was completed as scheduled in the third quarter.

Malfunction test CC08 scheduled for completion in second quarter of 1992 was completed in the first quarter of 1992 as part of additional simulator testing.

Malfunction test FW49 scheduled for completion 'in the first quarter of 1993 has been deleted.

Attachment to AEP:NRC:1134A Page 14 COOK NUCLEAR PLANT SIMULATOR REAL TIME TEST REPORT TEST RO. MTE CRT-1 COMPUTER REhL TIME TEST 11/05/91 CRT-1 COMPUTER REhL TIME TEST 01/04/92 CRT-1 COMPUTER REhL TIME TEST 03/12/93 CRT-1 COHPUTER REhI TIHE TEST 01/12/94

Attachment to AEP:NRC:1134A Page 15 COOK NUCLEAR PLANT SIMULATOR NORMAL. PLANT EVOLUTION PERFORMANCE TESTING DEQRIPZION NPE-1 RCS FILL AND VENT 02-OHP-4021. 002. 001 03/31/81 RCS FILL AND VENT 02-OHP-4021. 002. 001 01/04/92 RCS PILL AND VENT 02-OHP-4021.002.001 02/07/93 RCS PILL AND VENT 02-OHP-4021.002.001 01/17/94 NPE-2 HEATUP FROH BODE 5 TO HODE 3 02-OHP-4021.001.001 06/30/91 HEATUP FROM NODE 5 TO BODE 3 02-OHP-4021.001.001 04/12/92 HEATUP FRCH MDE 5 TO BODE 3 02-OHP"4021.001.001 06/11/93 HEATUP FROH NODE 5 TO BODE 3 02-OHP-4021.001.001 06/26/94 NPE-3 REACTOR STARTUP 02-OHP-4021.001.002 09/30/91 REACTOR STARTUP 02-OHP-4021.001.002 04/18/92 REACTOR STARTUP 02-0HP-4021.001.002 09/23/93 NPE-4 POWER ESCALATION 02"OHP-4021. 001. 006 12/31/91 POWER ESCALATION 02-0HP-4021.001.006 10/23/92 POWER ESCALATION 02-0HP-4021.001.006 11/19/93 NPE-5 POWER REDUCTION 02-OHP-4021. 001. 003 06/28/91 POWER REDUCTION 02-0HP-4021.001.003 04/16/92 POWER REDUCTION 02-OHP"4021.001.003 05/28/93 POWER REDUCTION 02-0HP-4021-001.003 06/27/94 NPE-6 PLANT COOLDOWN 02-OHP"4021.001.004 09/30/91 PLANT COOLDOWN 02-0HP-4021.001.004 06/20/92 PLANT COOLDOWN 02-0HP-4021.001.004 09/10/93 NPE-7 RCS DRAIN TO HALF LOOP 02-OHP-4021.002.005 12/31/91 RCS DRAIN TO HALF LOOP 02-0HP-4021.002.005 12/12/92 RCS DRAIN TO HALF LOOP 02-OHP-4021.002.005 12/15/93

Attachment to AEP:NRC:1134A Page 16 COOK NUCLEAR PLANT. SIMULATOR STEADY STATE TESTING REPORT TEST HO. TZTIZ SS-01 30X POHER STEADY STATE TEST 12/07/91 SS-01 30Z POHER STEADY STATE TEST 03/26/92 SS-01 30Z POHER STEADY STATE TEST 03/16/93 SS-01 30X POWER STEADY STATE TEST 03/28/94 SS-02 60Z POWER STEADY STATE TEST 06/27/91 SS-02 60Z POWER STEADY STATE TEST 06/24/92 SS-02 60Z POHER STEADY STATE TEST 06/18/93 SS-02 60Z POHER STEADY STATE TEST 06/26/94 SS-03 90X POWER STEADY STATE TEST 07/22/91 SS-03 90X POHER STEADY STATE TEST 08/28/92 SS-03 90X POHER STEADY STATE TEST 09/20/93 SS-04 100Z POHER STEADY STATE TEST 12/07/91 SS-04 100Z POHER STEADY STATE TEST 12/29/92 SS-04 100X POWER STEADY STATE TEST 11/30/93

Attachment to AEP:NRC:1134A Page 17 COOK NUCLEAR PLANT SIMULATOR TRANSIENT TESTS DESCRIPTION TRANSIENT 01 MANUAL REACTOR TRIP 04/05/91 TRANSIENT 01 MANUAL REACTOR TRIP 02/17/92 TRANSIENT 01 MANUAL REACTOR TRIP 03/12/93 TRANSIENT 01 MANUAL REACTOR TRIP 01/22/94 TRANSIENT 02 TRIP OF ALL MAIN PEEDPUMPS 06/17/91 TRANSIENT 02 TRIP OF ALL HAIN FEEDPUMPS 06/22/92 TRANSIENT 02 TRIP OF ALL MAIN FEEDPUMPS 06/11/93 TRANSIENT 02 TRIP OF ALL MAIN PEEDPUMPS 06/26/94 TRANSIENT 03 CLOSURE OF ALL MSIV'6 10/23/91 TRANSIENT 03 CLOSURE OF ALL HSIV'S 08/28/92 TRANSIENT 03 CLOSURE OF ALL HSIV'S 09/23/93 TRANSIENT 04 TRIP OF ALL RCP'S 11/16/91 TRANSIENT 04 TRIP OF ALL RCP'S 10/26/92 TRANSIENT 04 TRIP OF ALL RCP'S 10/26/93 TRANSIENT 05 TRIP OF RCP f23 04/05/91 TRANSIENT 05 TRIP OF RCP f23 02/17/92 TRANSIENT 05 TRIP OF RCP f23 03/12/93 TRANSIENT 05 TRIP OF RCP f23 01/22/94 TRANSIENT 06 MAIN TURBINE TRIP W/O RX TRIP 06/17/91 TRANSIENT 06 MAIN TURBINE TRIP W/0 RX TRIP 06/22/92 TRANSIENT 06 HAIN TVRBINE TRIP W/0 RX TRIP 06/21/93 TRANSIENT 06 MAIN TURBINE TRIP W/O RX TRIP 06/26/94 TRANSIENT 07 MAX POWER RAHP 100X-752-1002 11/16/91 TRANSIENT 07 MAX POWER RAMP 100X-75X-IQQX 08/28/92 TRANSIENT 07 MAX POWER RAMP 100X-752-1002 09/17/93 TRANSIENT 08 MAX SIZE LOCh WITH BLACKOUT 12/10/91 TRANSIENT 08 HAX SIZE LOCA WITH BLACKOUT 10/26/92 TRANSIENT 08 HAX SIZE LOCA WITH BLACKOUT 12/06/93 TRANSIENT 09 HAX SIZE MAIN STEAHLINE RUPTURE 04/05/91 TRANSIENT 09 MAX SIZE HAIN STEAMLINE RUPTVRE 02/17/92 TRANSIENT 09 HAX SIZE MAIN STEAHLINE RUPTURE 03/12/93 TRANSIENT 09 MAX SIZE HAIN STEAHLINE RUPTURE 01/21/94 TRANSIENT 10 SLOW RCS DEPRESSURIZATION TO SATURATION 06/17/91 TRANSIENT 10 SLOW RCS DEPRESSURIZATION TO SATVRATION 10/26/92 TRANSIENT 10 SLOW RCS DEPRESSURIZATION TO SATURATION 06/14/93 TRANSIENT 10 SLOW RCS DEPRESSURIZATION TO SATVRATION 06/26/94

Attachment to AEP:NRC:1134A Page 18 COOK NUCLEAR PLANT SIMULATOR SPECXAL TRANSXENT TESTXNQ TEST NUMBER DESCRIPTION ST-01 NATURAL CIRC. COOLDOWN W/VESSEL HEAD VOID FORMATION 12/30/91 ST-01 NATURAL CIRC. COOLDOWN W/VESSEL HEAD VOID FORMATION 02/25/92 ST-Ol NATURAL CIRC, COOLDOWN W/VESSEL HEAD VOID FORMATION 03/12/93 ST-01 NATURAL CIRC. COOLDOWN W/VESSEL HEAD VOID FORMATION 03/30/94 ST-02 ANTICIPATED TRANSIENT WITHOUT SCRAM (ATWS) 12/09/91 ST-02 ANTICIPATED TRANSIENT WITHOUT SCRAM (ATWS) 06/24/92 ST-02 ANTICIPATED TRANSIENT WITHOUT SCRAM (ATWS) 06/11/83 ST-02 ANTICIPATED TRANSIENT WITHOUT SCRAM (ATWS) 06/10/84 ST-03 STEAM GENERATOR TUBE RUPTURE 08/28/92 ST-03 STEAM GENERATOR TUBE RUPTURE 09/24/93 ST-04 UNIT 2 REACTOR TRIP, NOVEMBER 13, 1885 12/30/91 ST-04 UNIT 2 REACTOR TRI P ~ NOVEMBER 13 y 1885 01/15/93 ST-04 UNIT 2 REACTOR TRIP, NOVEMBER 13, 1985 12/06/93

Attachment to AEP:NRC:1134A Page 19 COOK NUCLEAR PLANT SIMULATOR MALFUNCTION TEST REPORT YEAR 1990 CC02 CCW PUMP FAILURE TO AUTO START 09/05/90 1990 CC06 SEAL WATER HX TUBE LEAK 09/05/90 1990 CH01 CONTAIN~ PRESS. RELIEF VLV PAILURE 10/01/90 1990 CS03 REFUELING WATER STORAGE TANK LEAK 10/01/90 1990 CV04 LETDOWN LINE ORIFICE ISO. VLV FAILURE 10/01/90 1990 CV09 LETDOWN TEMPERATURE CONTROL FAILURE ll/13/90 1990 1990 1990 CV13 CV17 CV26 CHARGZNG PUMP TRIP VOLUME CONTROL TANK REACTOR COOLANT PUMP L~

fl SEAL FAILURE 10/01/90 10/01/90 10/02/90 1890 CV31 BACKPRESSURE CONT VLV FAILURE-QRV"200 10/03/80 1990 CW02 CW PUMP DISCHARGE VALVE FAILURE 09/05/80 1990 ED03 LOSS OF RESERVE AUXILIARYTRANSFORMER 10/02/90 1990 ED06 LOSS OF 600 VAC BUS 03/25/90 1990 ED07 LOSS OF 460 VAC BUS 11/21/90 1990 ED11 LOSS OF 250 VDC BUS 03/25/90 1990 ED15 LOSS OF VITAL INST BUS STATIC SWITCH 03/25/90 1990 ED16 AUXILIARIES AUTO BUS TRANSPER FAILURE 10/03/90 1980 ED19 ELECTRICAL GRID LOAD REJECTION 07/16/90 1990 ED20 ANN PANEL POWER SUPPLY FAILURE 09/06/90 1990 ED24 LOSS OF 250 VDC TRAIN "N" BATTERY 09/07/90 1990 EG03 MG AUTO VOLTAGE REG FAILURE TO MANUAL 09/07/80 1980 EG07 DG SPEED CONTROL FAILURE 10/03/90 1980 EG11 DIESEL GENERATOR FAILURE TO TRIP 09/11/90 1990 EG15 MG SEAL OIL UNIT PIPING RUPTURE 09/11/90 1990 FP05 CONTROL ROOM CABLE VAULT PIRE 09/11/90 1990 FW05 MAIN FEEDPUMP TURBINE TRIP 10/03/90 1980 FW16 HP HTR 46 LVL CONTROL VALVE FAILURE 09/12/90 1990 FW22 HP HTR f5 LVL CONTROL VALVE FAILURE 09/24/80 1990 FW26 LP HTR f4 LVL CONT TRANSMITTER PhIL 10/24/80 1990 FW30 LP HTR g3 LVL CONTROL VALVE FAILURE 1O/24/8O 1990 FW34 CONDENSATE BOOSTER PUMP TRIP 10/23/90 1990 FW36 LOSS OP CONDENSER VACUUM 09/13/90 1990 FW42 CONDENSATE STORAGE TANK LEAK 09/24/90 1990 FW46 AUX FEEDPUMP TRIP 09/24/90 1990 FW50 TDAFW PUMP SPEED CONTROLLER FAILURE 09/24/90 1990 FW54 FDWTR RUPT OUTSIDE CONTAINMENT 04/09/90 1990 FW56 FEED PUMP STEAM SUPPLY CONT FAILURE 09/24/90 1990 MS03 MAZN STM LINE BREAK OUTSIDE CONT 10/24/90 1990 MS06 SG STOP VALVE DRIFTS SHUT 10/24/90 1990 MS12 MSR DRAIN TK ALT DRAIN LVL CONT FAIL 12/27/90 1990 MS17 STEAM SEAL CONTROLLER OSCILLATION 09/24/90 1990 NI02 SOURCE RANGE HV FAILURE TO DEENERGIZE 12/27/90 1990 NZ06 INTERMEDIATE RANGE MONITOR FAILURE 09/24/90 1990 NI10 POWER RANGE CHANNEL FAILURE ll/12/90 1990 NI14 INTERMEDIATE RANGE CHANNEL BLOWN FUSE 11/13/90 1990 RC03 RCS LEAK 09/24/90 1990 RC07 REACTOR COOLANT PUMP LOCKED ROTOR 11/13/90 1990 RC13 RCP UPPER BEARING OIL RESERVOIR LEAK 11/13/90 1990 RC17 PRESSURIZER PORV FAILURE 11/14/90 1990 RC24 STEAM GENERATOR TUBE LEAK 09/25/90 1990 RC26 PRESSURIZER INSTRUMENT LINE LEAKAGE 11/13/90 1990 RD04 STUCK CONTROL ROD (UNTRIPPABLE) 09/25/90 1990 RD06 IN-HOLD-OUT SWITCH FAILURE 09/25/90 1990 RD12 FAILURE OF CONTROL RODS TO MOVE 11/14/90

Attachment to AEP:NRC:L134A Page 20 COOK NUCLEAR PLANT SIMJLATOR MALPUNCTXON TEST REPORT YEAR TITLE 1990 RD16 IRPZ FAILURE 11/21/00 1000 RH02 RHR PUMP SEAL FAILURE 09/25/90 1990 RH06 RHR INJ HDR RELIEF VALVE FAIL (SV-1Q4) 12/27/00 1SSO RH11 RHR RET FLOH TRANS FAILURE (IFI 335) 09/25/90 1080 RH15 SI ACCUMULATOR N2 PRESSURE LOSS 11/21/90 1090 RP03 PAILURE OF REACTOR TRIP BREAKER 00/25/00 1990 RP08 SPVRIOUS FEEDHATER ISOLATION TRIP 00/25/90 1990 RP12 SPURIOUS ACTUATION OF SZ 00/26/00 1090 RP16 FAILURE OF CI PHASE B TO AUTO ACTUATE 09/26/00 1080 RP20 TRAIN "B" K600 RELAY FAILURES 00/27/00 1090 RX04 PRESSURIZER PRESSURE TRANS FAILURE 12/27/90 1090 RX08 PZR SPRAY UALVE AUTO CONTROL PAILURE 11/14 ISO 1090 RX12 MS RELIEF VLV CONTROLLER OSCILLATION 12/27/00 1990 RX16 STEAM DUMP "PRES CONT" ERRATIC OPS 12/27/90 1890 RX20 SG STEAM FLOH TRANSMITTER PAILURE 12/27/90 1090 RX24 FH CONTROL VALVE CONTROLLER PAILVRE 11/14/90 1890 RX27 FEED PUMP DP CONTROLLER PAILURE 07/10/00 1990 RX28 LOSS OF 480V MOC 00/26/90 1990 SH01 NON ESSENTIAL SERVICE MATER PUMP TRIP 09/26/00 1090 SH05 ESH PIPING RUPTURE 09/26/SO 1990 TC02 MAIN TURBINE FAILURE TO TRIP 11/14/80 1090 TC06 MAIN TURBINE ERRATIC CONTROL VALVE 09/26/90 1990 TC11 AUTO LOAD SET OSCILLATION 12/26/80 1SQO TP02 TVRBZNE AUX COOLING PIPING RUPTURE 12/26/00 1990 TUQ3 MAIN TURBINE HIGH UIBRATION 00/26/90 1001 CC03 CCMPONENT COOLING MATER RUPTURE 09/18/91 1991 CC07 COMPONENT COOLING HX TUBE RUPTURE 02/16/91 1S91 CH02 CONTAIN. PRESSURE TRANSMITTER FAILURE 05/15/91 1881 CS04 RHST LEVEL TRANSMITTER FAILURE 11/13/91 1991 CV05 LETDOHN HEAT EXCHANGER TUBE LEAK 02/16/01 1091 CV10 NORMAL CHG LINE LEAK INSIDE CONTAIN 07/02/01 1901 CV14 CHARGING PUMP SUCTION LINE LEAKAGE 10/23/01 lQS1 CV20 INADVERTENT BORATZON 02/16/91 1991 CV27 Rl~MTOR COOLANT PUMP 42 SEAL FAILURE 05/15/91 1991 CV32 PH FLOH TRANSMITTER (QFC 422) FAILURE 07/10/01 1001 CH03 TRAVELING HATER SCREEN FOVLING 05I 15/81 1991 ED04 LOSS OF EP SUPPLY TRANS TR-12 EP 10/24/01 1991 ED21 4KV/600V AUX TRANSFORMER LOSS 09/12/91 1801 EG04 MG AUTO VOLTAGE REGVLATOR FAILURE 02/16/01 1091 EGOS DG SPEED GOVERNOR FAILURE 05/15/01 1901 EG12 DG OUTPUT PREAKER FAILURE TO AUTO CLS 09/12/01 1091 FP01 PIRE PROTECTION SYSTEM RUPTURE 10I23/91 1091 FM01 MAIN FEEDHATER RUPTVRE AT SG INLET 11/13/01 1091 FH06 MFP TURBINE SHEARED SHAFT (UNRECOU) 02/16/01 1991 FM15 FEEDHATER CONTROL UALVE FAILURE 02/16/91 10Sl FH19 HP HEATER f6 TUBE RUPTURE 05/15/01 1091 PH23 =-

HP HEATER f5 TUBE RUPTURE 07/10/01 1991 FH27 LP HTR 44 LVL CONTROL UALVE FAILURE 05/15/91 1901 FH31 LP HEATER f3 TUBE RUPTURE 11/13/91 1991 FH35 COND BOOSTER PP DISC PIPING RUPTVRE 07/10/01 1991 FH39 CONDENSER TUBE LEAK 11/13/01 1091 FH43 HEATER DRAIN PUMP TRIP 02/18/91 1991 FH47 AUX FEEDPVMP SUCTION LINE LEAKAGE 05/16/81 1991 FH51 TDAFP TRIP A THROTTLE VALVE FAILURE 07/19I91

Attachment to AEP:NRC:1134A Page 21 COOK NUCLEAR PLANT SIMULATOR MAL1WNCTXON TEST REPORT 1081 IA01 PLANT AIR COMPRESSOR TRIP 02/18/01 1001 IA05 CONT AIR SYS RUPTURE IN CONTAINMENT 11/13/01 1091 HS04 HS LINE BREAK DOWNSTREAM SG STOP VLVS 03/16/91 1001 HSQQ HSR TUBE RUPTURE 05/16/01 1001 HS13 HSR DRAIN TK ALT LVL CONT VALVE PhIL 07/26/01 1091 MS16 STEAM DUMP CONTROL VALVE PAILURE 05/16/81 1091 NI03 INCORRECT SR CHANNEL RESPONSE ll/05/01 1001 NI07 IR IMPROPER COHPENSATION 03/16/01 1991 NI11 PR CHANNEL OUTPUT OSCILLATION 05I16I01 10S1 NI15 POWER RANGE CHANNEL BLOWN FVSE 08/16/91 1901 RC04 PRESSURIZER SURGE LINE LEAK 11/13/01 1991 RC06 REACTOR COOLANT PUHP SHAFT BREAK 03/16I01 1001 RC14 PZR HIGH GAS CONCENTRATION IN VPR SP 00/18/Sl 1001 RC10 PRESSURIZER SAFETY VALVE FAXLURE 05/16/01 1091 RC25 SG BD LINE LK DOWNSTREAM CONT ISOL 11/13/01 1991 RD01 DROPPED CONTROL ROD 03I16I91 1091 RD05 EJECT OF RD WITH RVPT MECH HOUSING 05/16/81 1001 RDOQ UNCONT ROD MOTION DEMAND (AUTOHATIC) 09/12/01 1001 RD13 ROD GROUP FAILURE TO HOVE 09/12/91 1001 RD1'7 ROD GROUP STEP COUNTER FAILURE 11/13/01 1S91 RH03 RHR HX BYPASS FLOW CONTROL VALVE PhIL 11/05I01 1091 RH07 RHR NORMAL CD SUC LINE LK INSIDE CONT 11/05/01 1901 RH12 SI LOOP CHECK VALVE LEAKAGE 03/16I91 1991 RM01 AREA RADIATION MONITOR FAILURE 12/RO/91 1901 RP05 REACTOR (XX)LANT FMW TRANS FAILURE 05/16/01 1991 RP09 FAILURE OF FW ISOLATION TRIP TO OCCUR 07/10/01 1001 RP13 FAILURE OF CI PHASE A TO AUTO ACTUATE 11/13/01 1901 RP17 FAILURE OF CI PHASE B TO HANUAL ACT 03/16/01 1001 RXO1 RCS HOT LEG PRESSURE TRANS FAILVRE 05/17/01 1001 RX05 PZR LVL TRANS FAILURE (PROT C)(ANNEL) 07/00/01 1S91 RXQS PZR PRES MASTER CONXROLLER FAILURE 11/05/01 1091 RX13 STEAH DUMP "TAVG" CONTROLLER FAILURE 03/16/91 1891 RX17 SG PRESSURE TRANSMITTER FAILURE 05/16/01 1891 RX21 SG PEED FLOW TRANSHITTER PAILURE 07/00/01 1991 RX25 FEEDWATER CONTROL VALVE OSCILLATION 11/05/91 1081 SI01 SAFETY INJECTION PUMP TRIP 09/12/Sl 1991 SW02 NESW PIPING RUPTURE IN 'XURB BLDG 03/16/01 1091 SW06 FP TURB OIL COOLING CONTROLLER FAILURE 05/17/91 1901 TCQ3 MAIN TURBINE AUTO TRIP FAILURE 11/05/01 1091 TC07 MAIN TVRBINE INTERCEPT VALVE FAILURE 11/10/01 1001 TC12 MAIN TURBINE SPEED SIGNAL FAILURE 11/05/91 1091 TP03 HG STATOR COOLING SYSTEH RUPTURE 05/17/91 1001 TU05 MAIN TURBINE BEARING FAILURE 07/10/91 1002 CCQ4 MISC CCW HDR RUPTURE INSIDE CONTAIN. 03/23/02 1892 CC08 CCW LEAKAGE INTO RCP BRNG OIL RES. 02/24/02 109R CS01 CONTAINMENT SPRAY PUMP TRIP 06/02/02 1002 CV01 LETDOWN LINE RUPTURE INSIDE CONTAIN. 08/17/02 1082 CV06 ORV-301 FAILURE 11/R3/02 1092 CV11 NORMAL CHG LINE LEAK OUTSIDE CONTAIN 01/04/92 1882 CV15 VCT LEVEL CONTROL VALVE FAILURE 05/27/92 1092 CV21 INADVERTENT DILUTION 07/13/02 1082 CV28 REACTOR COOLANT PUMP f3 SEAL PAILURE 12/28/02 1092 CV33 Bh FLOW CONTROLLER (QFC-421) FAILURE Ql/04/02 1992 ED01 LOSS OF 345KV BUS NO. 1 06/17/02

Attachment to AEP:NRC:1134A Page 22 COOK NUCLEAR PLANT SIMULATOR MALFUNCTION TEST REPORT 1902 ED10 LOSS OP 120 VAC CONTROL ROOH POWER 11/24/92 1902 ED22 LOSS OF SWITCHGEAR CONT POWER TRAIN B 06/02/02 1002 EGOS HG OUTPUT BREAKER FAILURE TO TRIP 08/17/92 1902 EG09 DG VOLTAGE CONTROL FAILURE 11/24/02 1992 EG13 DG OUTPUT BREAKER FAILURE TO CLOSE 01/04/02 1902 FP02 INADV ACT OP CHARCOAL FILT PIRE PROT. 06/15/02 1002 FW02 MFW RUPTURE BEFORE SG CHECK VALVE 08/28/02 1092 FW07 HAIN FEEDPUMP TURBINE BEARING FAILVRE 12/11/02 1092 FW16 HP HTR 46 LVL CONT TRANSHITTER FAIL 02/11/02 1002 FW20 HP HTR 45 LVL CONT TRANSHITTER FAIL 06/15/02 1092 FW24 HP HEATER g5 STEAH INLET RUPTURE 01/04/02 1002 FW28 I.P HEATER 44 TUBE RUPTURE 08/28/02 1002 FW32 LP HEATER f3 STEAH INLET RUPTVRE 06/15/92 1002 FW36 COND BOOSTER PP RECIRC VALVE FAILURE 03/23/92 1092 FW40 HOZWELL LEVEL CONTROLLER PAILVRE 12/10/92 1002 FW44 HEATER DRAIN PUMP BEARING FAILURE 05/27/92 1002 FW48 AVX FEEDPUMP AUTO START FAILURE 08/28/02 1002 FW52 STEAH BOUND APW PUMP 09/24/92 1092 ZA02 PLANT AIR SYSTEH RUPTURE 12/28/02 1092 MS01 MS LINE BREAK AT SG EXIT 02/11/02 1002 HS05 HAIN STEAM POWER RELIEF VALVE LEAK 06/02/92 1092 MS10 HSR COIL DRAIN TAIlK LVL CONT FAILVRE 09/24/02 1002 HS14 HSR STEAM SUPPLY VALVE PAILURE 12/28/92 1092 HS21 AUX STH 150 0 HDR CONT VALVE FAILVRE 02/14/02 1092 NZ04 SR ENERGIZATION AT POWER (P10 FAIIVRE) 06/02/02 1S02 NZ08 PR CHANNEL UPPER DETECTOR FAILURE 08/28/92 1092 NI12 AVDIO COUNT RATE CHANIIEL FAILURE 12/10/02 1992 RC01 RCS COLD LEG LOOP RUPTURE 03/23/92 1002 RC05 REACTOR VESSEL HEAD FLANGE LEAK 12/10/02 1992 RC09 REACTOR COOLANT PUMP TRIP 02/14/92 1002 RC15 PRESSURIZER SPRAY VALVE FAILURE 08/15/02 1092 RC21 FRT RUPTURE DISC FAILURE 08/28/92 1002 RC26 FAILED PVEL ELEMENT 12/28/92 1092 RD02 BROKEN CONTROL ROD 02/14/92 1092 RD06 UNCONT ROD BANK CONTINUOUS WITHDRAWAL 06/15/92 1992 RD10 CR HOVE OPPOSITE TO DEMAND SIGNAL 08/28/92 1092 RD14 IMPROPER BANK OVERLAP 11/11/92 1902 RD18 ROD CONTROL HG SET TRIP 06/02/02 1992 RH04 RHR HX FLOW CONTROL VALVE PAILURE 06/15/92 1002 RH08 RWST SUPPLY LINE TO RHR PUMP RUPTURE 08/28/92 1992 RH13 SI ACC TANK CHECK VALVE LEAKAGE 12/19/92 1902 RM02 PROCESS RADIATION MONITOR FAILVRE 03/11/92 1992 RP06 SPURIOUS STEAH LINE ISOLATION 01/21/02 1092 RP10 FAILURE OF SZ TO ACTUATE-AUTOHATIC 06/02/92 1002 RP14 FAILURE OF CZ PHASE h TO MANUAL ACT 08/28/02 1002 RP18 SPURIOUS ACTUATION OF CI PHASE B 12/19/02 1092 RX02 RCS HOT LEG TEMP TRANS FAILURE (NR) 01/21/02 1092 RX06 PZR CAL LEVEL TRANSHITTER FAILURE 05/27/92 1092 RX10 PZR WATER LEVEL CONT OSCILLATION 09/24/92 1092 RX14 STEAM DUMP "PRES" CONTROLLER FAILURE 12/28/92 1002 RX18 HS TURB BYPASS HDR PRESS TRANS FAILURE 01/21/02 1092 RX22 SG PROGRA)%ED LEVEL SIGNAL FAILURE 05/27/92 1992 RX26 FP TURBINE SPEED CONTROLLER FAILVRE 08/28/02 1092 SI02 SAPETY INJECTION PUMP SHEARED SHAFT 12/28/02

Attachment to AEP:NRC:1134A Page 23 COOK NUCLEAR PLANT SIMULATOR MALFUNCTION TEST REPORT TITLE 1992 SW03 NESW RUPT ON LWR CONT VENT CLR SUP 02/ll/92 1992 SW07 MT OIL TEMPERATURE CONTROLLER FAILURE 06/15/92 1992 TC04 MAIN TURBINE STOP VALVE FAILURE 08/26/92 1992 TC09 MAIN GENERATOR LOAD LIMITER PAILURE 08/26/92 1992 TC13 TURBINE RUNBACK PAILURE 12/19/92 1992 TP05 STATOR COOLING WTR SYS HIGH COND 12/26/92 1992 TU06 TURBINE BLADE EJECTION 02/14/92 1993 CC01 COMPONENT COOLING WATER PUMP TRIP 02/27/93 1993 CC05 MISC CCW HDR RUPTURE IN AUX BUILDING 04/26/93 1993 CC09 CCW.LEAK ON RHR PUMP SUPPLY LINE 08/24/93 1993 CC10 CCW INLEAKAGE INTO RCP LOWER BRNG OIL RSVR 11/23/93 1993 CS02 CONTAIN. SPRAY PUMP SUCTION BLOCKAGE 11/20/93 1993 CV02 LETDOWN I INE RUPTURE OUTSIDE CONTAIN. 02/24/93 1993 CV08 LETDOWN LINE RELIEF VLV SV-51 LEAKAGE 04/26/93 1993 CV12 CCP FLOW CONTROL VALVE FAILURE 09/15/93 1993 CV16 VCT LEVEL TRANSMITTER FAILURE 11/20/93 1993 CV25 RCP THERMAL BARRIER HX RUPTURE 02/16/93 1993 CV30 REDUCED CCP CAPACITY 06/30/93 1993 CW01 CIRCULATING WATER PUMP TRIP 08/19/93 1993 ED02 LOSS OP AUXILIARYTRANSFORMER 11/20/93 1993 ED 05 LOSS OF 4160 VAC BUS 06/25/93 1993 ED08 LOSS OF 600V MCC 06/25/93 1993 ED12 LOSS OF 250 VDC POWER (TRAIN h) 06/27/93 1993 ED13 LOSS OF 250 VDC POWER (TRAIN B) 08/27/93 1993 ED14 LOSS OF 250 VDC BATTERY CHARGER 08/27/93 1993 ED17 LOSS OF PLANT LIGHTING 08/27/93 1993 ED18 GRID VOLTAGE OSCILLATION 09/03/93 1993 ED23 LOSS OF SWITCHGEAR CONT POWER TRAIN h 02/27/93 1993 ED25 LOSS OF 765/345KV TRANSFORMER BANK f4 09/03/93 1993 ED26 LOSS OF 765KV DUMONT LINE 09/13/93 1993 EG01 MAIN GENERATOR TRIP 04/26/93 1993 EG06 DIESEL GENERATOR TRIP 09/13/93 1993 EG10 DIESEL GENERATOR FAILURE TO START 11/20/93 1993 EG14 DG RUNNING RELAY FAILURE 02/27/93 1993 FP03 DIESEL GENERATOR ROCM C02 ACTUATION 05/31/93 1993 FW03 MFW RUPT BETWEEN PEEDFLOW ELMT & FRV 08/24/93 1993 FW12 FEEDPUMP TURBINE LUBE OIL SYSTEM LEAK ll/20/93 1993 FW17 HP HTR I6 LVL CONTROLLER AUTO PAILURE 03/10/93 1893 FW21 HP HTR t5 LVL CONTROLLER AUTO FAILURE 04/26/93 1993 FW25 HOTWELL PUMP TRIP 09/12/93 1993 FW29 LP HTR I3 LVL CONT TRANSMITTER PhIL 11/20/93 1993 FW33 LP HEATER BYPASS VALVE FAILURE 03/10/93 1993 FW37 HOTWELL PUMP DISCHARGE PIPING RUPTURE 04/26/93 1993 FW41 HW LEVEL CONTROL TRANSMITTER FAILURE 06/24/93 1993 FW45 HEATER DRAIN PUMP ELO VLV PAILS OPEN 11/20/93 1993 ZA03 CONTROL AIR COMPRESSOR TRIP 05/31/93 1993 IA04 CONT AIR SYS RUPT IN TURBINE BUILDING 09/13/93 1993 MS02 MAIN STEAM LINE BREAK AT SG EXIT 09/12/93 1993 MS06 STEAM GENERATOR SAFETY VALVE LEAK 11/20/93 1993 MS11 MSR COIL DRAIN TANK LVL CONT VLV FAIL 02/27/93 1993 MS16 STEAM SEAL CONTROLLER FAILURE 05/31/93 1993 NI01 SOURCE RANGE MONITOR FAILURE 09/13/93 1993 NI05 SOURCE RANGE CHANNEL SPIKES 11/23/93 1993 NI09 PR CHANNEL LOWER DETECTOR FAILURE 02/27/93

~ 1 Attachment to AEP:NRC:1134A Page 24 COOK NUCLEAR PLANT SIMULATOR MALPUNCTION TEST REPORT 1993 NI13 SOURCE RANGE INSTRUMENT BLOHN FUSE 05/31/93 1893 RC02 RCS HOT LEG LOOP LEAK 09/12/93 1993 RC06 RCS EMERGENCY VENT LEAKAGE 11/22/93 1983 RC10 RCS COLD LEG LEAK 09/13/83 1993 RC11 REACTOR COOLANT PUMP HIGH VIBRATION 02/27/93 1993 RC12 RCP LONER BEARING OIL RESERVOIR LEAK 11/13/93 1993 RC16 PRESSURIZER STEAM SPACE MANNAY LEAK 05/31/83 1983 RC23 STEAM GENERATOR TUBE RUPTURE 09/13/93 1993 RC27 RTD BYPASS MANIFOLD FLOH DEGRADATION 11/23/93 1993 RC29 S/G BLOHDOHN LINE LEAK UPSTREAM OF CIV 11/13/93 1993 RD03 STUCK CONTROL ROD (TRIPPABLE) 02/24/93 1993 RD07 UNCONT ROD BANK CONTINUOUS INSERTION 05/31/93 1993 RD11 AUTO CONTROL ROD SPEED PAILURE 06/24/93 1993 RD15 IRPI POHER LOSS 11/22/93 1993 RD19 IMPROPER ROD NORTH 12/13/93 1993 RH01 RHR PUMP TRIP 03/01/93 1993 RH05 RHR HEAT EXCHANGER TUBE LEAK 05/31/93 1993 RH09 RHR PUMP SUCTION PIPE RUPTURE 06/24/93 1993 RH14 SI ACCUMULATOR TANK LEVEL LOSS 11/23/93 1993 RM03 EBERLINE AREA RADIATION MONITOR FAILURES 11/29/93 1993 Z(P01 REACTOR TRIP ACB AUTO TRIP FAILURE 02/16/93 1993 RP07 FAILURE OF STEAM LINE ZSO TO ACTIVATE 05/31/93 1993 RP11 FAILURE OF SI TO ACTUATE-MANUALLY 06/26/93 1993 RP15 SPURIOUS ACTUATION OF CI PHASE h 11/22/93 1993 RP19 TRAIN "h" K600 RELAY FAILURES 03/10/93 1993 RP21 FAILURE OF FHI TRIP TO OCCUR 11/13/93 1993 RX03 RCS COLD LEG TEMP TRANS FAILURE (NR) 04/21/93 1993 RX07 REDUCED PRESSURIZER HEATER CAPACITY 09/12/93 1893 RX11 SG RELIEF VALVE CONTROLLER FAILURE 11/29/93 1893 RX15 STEAM DUMP SYSTEM FAILURE TO RESPOND 03/Ol/93 1893 RX19 TURBINE IMPULSE TRANSMITTER FAILURE 05/31/93 1993 RX23 SG LEVEL TRANSMITTER FAILURE 09/13/93 1993 RX29 FPC-250 TRANSMITTER FAILURE 12/10/93 1993 SZ03 HIGH HEAD SI LINE RUPTURE 02/24/93 1893 SN04 ESSENTIAL SERVICE RATER PUMP TRIP 04/26/93 1893 TC01 MAIN TURBINE TRIP 09/12/93 1993 TC05 MAIN TURBINE CONTROL VALVE FAILURE 11/23/93 1993 TC10 MAIN GEN OPERATING DEVICE FAILURE 03/01/93 1983 TP01 TURBINE AUX COOLING PUMP TRIP 04/26/93 1993 TU01 AUXILIARYLUBE OIL PUMP TRIP 09/13/83 1893 HD01 RELEASE OF RADIOACTIVE GAS FROM GDT 11/23/83 1994 CC02 CCH PUMP FAILURE TO AUTO START 01/12/94 1994 CH01 CONTAIN. PRESS. RELIEP VLV FAILURE 04/04/94 1894 CV04 LETDOWN LINE ORIFICE ISO. VLV FAILURE 04/04/94 1994 CV13 CHARGING PUMP TRIP 04/04/94 1994 CV17 VOLUME CONTROL TANK LEhlGKE 04/04/94 1994 CV31 BACKPRESSURE CONT VLV FAILURE-QRV-200 04/04/94 1994 ED02 LOSS OF AUXILIARYTRANSFORMER 01/12/94 1994 ED 06 LOSS OF 600 VAC BUS 01/15/94 1994 ED11 LOSS OF 250 VDC BUS 01/15/94 1984 ED15 LOSS OP VITAL INST BUS STATIC SWITCH 01/22/94 1994 EG07 DG SPEED CONTROL FAILURE 04/04/94 1994 EG15 MG SEAL OIL UNIT PIPING RUPTURE 01/22/94 1994 FW16 HP HTR f6 LVL CONTROL VALVE FAILURE 01/17/94

Attachment to AEP:NRC:1134A Page 25 COOK NUCLEAR PLANT SIMULATOR MALPUNCTION TEST REPORT TITLE 1004 FH22 HP HTR 45 LVL CONTROL VALVE FAILURE 01/17/94 1004 FW26 LP HTR ga LVL CONT TRANSMITTER FAIL o6/oa/oa 1004 FW34 CONDENSATE BOOSTER PUMP TRIP 06/04/04 1904 FH38 LOSS OP CONDENSER VACUUM 01/17/04 1004 FW46 AUX FEEDPUMP TRIP 01/17/04 1004 FH50 TDAFH PUMP SPEED CONTROLLER PAILURE 01/18/04 1904 FH54 FINTR RVPT OUTSIDE CONTAINMENT 06/04/04 1904 MS08 SG STOP VALVE DRIFTS SHUT 06/04/04 1904 MS17 STEAM SEAL CONTROLLER OSCILLATION 01/18/04 1904 NI02 SOURCE RANGE HV FAILURE TO DEENERGIZE 06/06/04 1994 NI14 INTERMEDIATE RANGE CHANNEL BLOWN FVSE 06/04/04 1004 RC13 RCP UPPER BEARING OIL RESERVOIR LEAK 06/04/04 1004 RC24 STEAM GENERATOR TUBE LEAK 01/18/04 1004 RC28 PRESSURIZER INSTRUMENT LINE LEAKAGE 06/04/04 1904 RD04 STUCK CONTROL ROD (UNTRIPPABLE) 01/18/04 1004 RH02 RHR PUMP SEAL FAILURE 01/22/04 1904 RH06 RHR INJ HDR RELIEF VALVE FAIL (SV-104) 06/06/04 1004 RH11 RHR RET FLOW TRANS FAILURE (IFI-335) 01/22/04 1004 RP08 SPVRIOUS FEEDWATER ISOLATION TRIP 01/22/04 1004 RP16 FAILURE OF CI PHASE B TO AUTO ACTUATE 01/22/04 1094 RX04 PRESSURIZER PRESSURE TRANS PAILURE 06/04/94 1004 RX12 MS RELIEF VLV CONTROLLER OSCILLATION 06/04/04 1094 RX20 SG STEAM FLOH TRANSMITTER FAILURE 06/04/04 1094 RX27 FEED PUMP DP CONTROLLER FAILURE 01/22/94 1094 TC06 MAIN TURBINE ERRATIC CONTROL VALVE 01/18/04 1004 TC11 ,AUTO LOAD SET OSCILLATION o6/oa/04 1904 TP02 TVRBINE AUX COOLING PIPING RUPTVRE 06/02/04

Attachment to AEP:NRC:1134A Page 26 DONALD C. COOK NUCLEAR PLANT SIMULATOR CERTIFICATION SCHEDULE The following pages consist of the Cook Nuclear Plant Simulator Certification Test schedule through 1998. This section describes testing for:

Testing required per Appendices A and B of ANSI 3.5, 1993 Malfunction Testing Test schedule has been modified from last report to include new malfunctions added to the simulator. Transient test 411 has been added to the schedule to incorporate change of ANSI 3.5 in the 1993 revision.

All malfunctions are scheduled to be completed on a four year rotation with approximately 25% performed annually.

Attachment to AEP:NRC:113/lA Page 27 COOK NUCLEAR PLANT SIMULATOR ANSI 3.5 APPENDICIES A AND B ANNUAL TESTING SCHEDULE CRT" 1 NPE-1 NPE-2 NPE-3 NPE-4 NPE-5 NPE-6 NPE-7 SS-01 SS-02 SS-03 SS-04 ST-01 ST-02 ST-03 ST-04 TMS-01 TMS-02 TMS"03 TRANS-04 TMS-05 TMS-06 TMS-07 TMS-08 TRANS-09 TRANS-10 TRANS-ll TEST DESCRIPTIONS:

CRT-1 COHPUTER REAL TIHE TEST NPE-1 RCS FILL AND VENT NPE-2 COLD SHUTDOWN TO HOT STANDBY NPE-3 REACTOR STARTUP NPE-4 PLANT STARTVP/POWER ESCALATION NPE-5 POWER REDVCTION NPE-6 PLANT COOLDOWN NPE-7 RCS DRAIN SS-1 STEADY STATE TEST 1 SS-2 STEADY STATE TEST 2 SS-3 STEADY STATE TEST, 3 SS-4 STEADY STATE TEST 4 ST-1 NATURAL CIRCULATION COOLDOWN W/VESSEL HEAD VOID FORHATION ST-2 ANTICIPATED TRANSIENT WITHOUT SCRAM (ATWS)

ST-3 STEAM GENERATOR TUBE RUPTVRE ST-4 UNIT 2 REACTOR TRIP, NOVEHBER 13, 1985 TMS-01 HANVAL REACTOR TRIP TMS-02 TRIP OF ALL HAIN FEEDPUHPS TMS-03 CLOSURE OF ALL HSIV'S TMS-04 TRIP OF ALL REACTOR COOLANT PUHPS TMS-05 TRIP OP REACTOR COOLANT PIMP f23 TMS-06 HAIN TURBINE TRIP W/0 REACTOR TRIP TMS-07 HAXIHVH POWER RAHP 1002-752-1002 TMS-08 HAXIHVH SIZE LOCA WITH BLACKOUT TMS-09 HAXIHVH SIZE HAIN STEAHLINE RUPTURE TRANS-10 SLOW RCS DEPRESSURIZATION TO SATURATION TMS-ll LOAD RE JECTION

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Attachment to AEP:NRC:1134A Page 28 COOK NUCLEAR PLANT SIMULATOR MALFUNCTION TEST SCHEDULE YEAR 1894 CC06 SEAL WATER HX TUBE LEAK 1994 CS03 REFUELING WATER STORAGE TANK LEAK 1894 CV09 LETDOWN TEHPERATURE CONTROL FAILURE 1894 1894 CV26 CM02 REACTOR COOLANT PUMP fl SEAL PAILURE CW PUMP DISCHARGE VALVE FAILURE 1994 ED03 LOSS OF RESERVE AUXILIARYTRANSFORHER 1994 ED07 LOSS OF 480 VAC BUS 1994 ED16 AUXILIARIES AUTO BUS TRANSFER FAILURE 1994 ED19 ELECTRICAL GRID LOAD REJECTION 1894 ED20 ANN PANEL POWER SUPPLY FAILURE 1994 ED24 LOSS OF 250 VDC TRAIN "N" BATTERY 1994 EG03 HG AUTO VOLTAGE REG PAILVRE TO MANUAI 1984 EG11 DIESEL GENERATOR FAILURE TO TRIP 1984 FP05 CONTROL ROQH CABLE VAULT PIRE 1984 FWOS HAIN FEEDPUMP TURBINE TRIP 1994 FW30 LP HTR f3 LVL CONTROL VALVE PAILURE 1994 FW42 CONDENSATE STORAGE TANK LEAK 1994 FW56 PEED PUMP STEAM SUPPLY CONT PAIIURE 1994 MS03 HAIN STH LINE BREAK OUTSIDE CONT 1994 MS12 HSR DRAIN TK ALT DRAIN LVL CONT FAIL 1994 NI06 INTERMEDIATE RANGE HONZTOR FAILURE 1994 NZ10 POWER RANGE CHANNEL FAILURE 1894 RC03 RCS LEAK 1994 RC07 REACTOR COOLANT PUMP LOCKED ROTOR 1S94 RC17 PRESSllRIZER PORV FAILURE 1994 RD08 IN-HOLD-OUT SWITCH FAILURE 1994 RD12 FAILURE OF CONTROL RODS TO HOVE 1994 RD16 IRPI FAILURE 1994 RH15 SZ ACCUMULATOR N2 PRESSURE LOSS 1984 RP03 FAILVRE OF REACTOR TRIP BREAKER 19S4 RP12 SPURIOUS ACTUATION OP SI 1894 RP20 TRAIN "B" K600 RELAY FAILURES 1994 RX08 PZR SPRAY VALVE AUTO CONTROL PAILVRE 1994 RX16 STEAH DUMP "PRES CONT" ERRATZC OPS 1994 RX24 FW CONTROL VALVE CONTROLLER PAILURE 1S94 RX28 LOSS OF 480V HCC 1994 SWO1 NON ESSENTIAL SERVICE MATER PUMP TRIP 1994 SW05 ESW PIPING RUPTVRE 1994 TC02 MAIN TURBINE FAILURE TO TRIP 1994 TU03 MAIN TVRBINE HIGH VIBRATION 1995 CC03 COMPONENT COOLING WATER RUPTURE 1995 CC07 COHPONENT COOLING HX TUBE RUPTVRE 1895 CH02 CONTAIN. PRESSURE TRANSHITTER FAILURE 1995 CS04 RWST LEVEL TRANSHITTER FAILURE 1995 CV05 LETDOWN HEAT EXCHANGER TUBE LEAK 1SS5 CV10 NORMAL CHG LINE LEAK INSIDE CONTAIN 1995 CV14 CHARGING PUMP SUCTION LINE LEAKAGE 1995 CV20 INADVERTENT BORATION 1995 CV27 REACTOR COOLANT PUHP t2 SEAL FAILURE 1995 CV32 PM PLOW TRANSHITTER (QFC" 422) FAILVRE 1SS5 CW03 TRAVELING MATER SCREEN FOVLING 1S95 ED04 LOSS OF EP SUPPLY TRANS TR-12-EP 1995 ED05 LOSS OP 4160 VAC BUS 1S95 ED14 LOSS OF 250 VDC BATTERY CHARGER

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Attachment to AEP: NRC: 1134A Page 29 COOK NUCLEAR PLANT SIMULATOR MALPUNCTION TEST SCHEDULE 1995 ED18 GRID VOLTAGE OSCILLATION 1985 ED21 4KV/600V AUX TRANSFORMER LOSS 1985 EG04 MG AUTO VOLTAGE REGULATOR FAILURE 1995 EGOS DG SPEED GOVERNOR PAILURE 1995 EG12 DG OUTPUT PREAKER FAILURE TO AUTO CLS 1985 FP01 FIRE PROTECTION SYSTEM RUPTURE 1995 FW01 MAIN FEEDWATER RUPTURE AT SG INLET 1985 FW06 MFP TURBINE SHEARED SHAFT (UNRZCOV) 1995 FW15 FEEDWATER CONTROL VALVE FAILURE 1895 FW19 HP HEATER 46 TUBE RUPTURE 1895 FW23 HP HEATER t5 TUBE RUPTURE 1995 FW27 LP HTR f4 LVL CONTROL VALVE FAILURE 1895 FW31 LP HEATER f3 TUBE RUPTURE 1995 FW35 COND BOOSTER PP DISC PIPING RUPTURE 1995 FW38 CONDENSER TUBE LEAK 1995 FW43 HEATER DRAIN PUMP TRIP 1995 FW47 AUX FEEDPUMP SUCTION LINE LEAKAGE 1985 FW51 TDAFP TRIP a THROTTLE VALVE PAILURE 1995 ZA01 PLANT AIR CCMPRESSOR TRIP 1995 IA05 CONT AIR SYS RUPTURE ZN CONTAINMENT 1995 MS04 MS LINE BREAK DOWNSTREAM SG STOP VLVS 1995 MS09 MSR TUBE RUFIURE 1995 MS13 MSR DRAIN TK ALT LVL CONT VALVE PhIL 1995 MS18 STEAM DUMP CONTROL VALVE FAILURE 1985 NZ03 INCORRECT SR CHANNEL RESPONSE 1995 NZ07 IR IMPROPER COMPENSATION 1985 NI11 PR CHANNEL OUTPUT OSCILLATION 1995 NI15 POWER RANGE CHANNEL BLOWN FUSE 1895 RC04 PRESSURIZER SURGE LINE LEAK 1995 RC09 REACTOR COOLANT PUMP SHAFT BREAK 1995 RC14 PZR HIGH GAS CONCENTRATION ZN VPR SP 1995 RC19 PRESSURIZER SAFETY VALVE FAILURE 1995 RC25 SG BD LINE LK DOWNSTREAM CONT ISOL 1995 RC29 S/G BLOWDOWN LEAK UPSTREAM OF CIV 1995 RD01 DROPPED CONTROL ROD 1995 RDOS EJECT OF RD WITH RUPT MECH HOUSING 1985 RD09 UNCONT ROD MOTION DEMAND (AUTOMATIC) 1995 RD13 ROD GROUP FAILURE TO MOVE 1895 RD17 ROD GROUP STEP COUNTER PAILURE 1995 RH03 RHR HX BYPASS FLOW CONTROL VALVE PAIL 1895 RH07 RHR NORMAL CD SUC LINE LK INSIDE CONT 1995 RH12 SI LOOP CHECK VALVE LEAKAGE 1995 RM01 AREA RADIATION MONITOR PAILURE 1995 RP05 REACTOR COOLANT FLOW TRANS FAILURE 1995 RP09 FAILURE OF FW ISOLATION TRIP TO OCCUR 1995 RP13 FAILURE OF CI PHASE A TO AUTO ACTUATE 1995 RP15 SPURIOUS ACTUATION OF CI PHASE h 1995 RP17 FAILURE OF CI PHASE B TO MANUAL ACT 1995 RX01 RCS HOT LEG PRESSURE TRANS FAILURE 1895 RX05 PZR LVL TRANS FAILURE (PROT CHANNEL) 1995 RX09 PZR PRES MASTER CONTROLLER FAILURE 1995 RX13 STEAM DUMP "TAVG" CONTROLLER FAILURE 1895 RX17 SG PRESSURE TRANSMITTER FAILURE 1995 RX21 SG FEED FLOW TRANSMITTER FAILURE

~s Attachment to AEP: NRC: 1134A I'age 30 COOK NUCLEAR PLANT SIMULATOR MALFUNCTXON TEST SCHEDULE 1995 RX25 FEEDWATER CONTROL VALVE OSCILLATION 1995 SI01 SAFETY INJECTION PUMP TRZP 1995 SW02 NESW PIPING RUPTURE IN TURB BLDG 1995 SW06 PP TURB OIL COOLING CONTROLLER FAILURE 1995 TC03 MAIN TURBINE AUTO TRIP FAILURE 1995 TC07 MAIN TURBINE INTERCEPT VALVE FAILURE 1995 TC12 MAIN TURBINE SPEED SIGNAL FAILURE 1995 TP03 MG STATOR COOLING SYSTEM RUPTURE 1995 TU01 AUXILIARYLUBE OIL PUMP TRIP 1995 TU05 MAIN TURBINE BEARING FAILURE 1996 CC04 MISC CCW HDR RUPTURE INSIDE CONTAIN.

1996 CC06 CCW LEAKAGE INTO RCP BRNG OIL RES.

1996 CS01 CONTAINMENT SPRAY PUMP TRIP 1996 CV01 LETDOWN LINE RUPTURE INSIDE CONTAIN.

1996 CV06 QRV-301 FAILURE 1996 CV11 NORMAL CHG LINE LEAK OUTSIDE CONTAIN 1996 CV15 VCT LEVEL CONTROL VALVE FAILURE 1996 CV21 INADVERTENT DILUTION 1996 CV26 REACTOR COOLANT PUMP f3 SEAL FAILURE 1996 CV33 Bh FLOW CONTROLLER (QFC-421) FAILURE 1996 ED01 LOSS OF 345KV BUS NO. 1 1996 ED06 LOSS OF 600V MCC 1996 ED10 LOSS OF 120 VAC CONTROL ROOM POWER 1996 ED17 LOSS OP PLANT LIGHTING 1896 ED22 LOSS OF SWITCHGEAR CONT POWER TRAIN B 1996 ED26 LOSS OF 765KV DUMONT LINE 1996 EG05 MG OUTPUT BREAKER FAILURE TO TRIP 1986 EG09 DG VOLTAGE CONTROL FAILURE 1996 EG13 DG OUTPUT BREAKER FAILURE TO CLOSE 1986 FP02 INADV ACT OF CHARCOAL FILT FIRE PROT.

1886 FW02 MFW RUPTURE BEFORE SG CHECK VALVE 1996 FW07 MAIN FEEDPUMP TURBINE BEARING FAILURE 1986 FW16 HP HTR g6 LVL CONT TRANSMITTER FAIL 1996 FW20 HP HTR f5 LVL CONT TRANSMITTER FAIL 1996 FW24 *HP HEATER fS STEAM INLET RUPTURE 1986 FW26 LP HEATER f4 TUBE RUPTURE 1996 FW32 LP HEATER f3 STEAM INLET RUPTURE 1986 FW36 COND BOOSTER PP RECIRC VALVE PAILURE 1996 FW40 HOTWELL LEVEL CONTROLLER FAILURE 1996 FW44 HEATER DRAIN PUMP BEARING PAILURE 1996 FW46 AUX FEEDPUMP AUTO START FAILURE 1996 FW52 STEAM BOUND AFW PUMP 1996 IA02 PLANT AIR SYSTEM RUPTURE 1996 IA04 CONT AIR SYS RUPT IN TURBINE BUILDING 1986 MS01 MS LINE BREAK AT SG EXIT 1996 MS05 MAIN STEAM POWER RELIEF VALVE LEAK 1996 MS10 MSR COIL DRAIN TANK LVL CONT FAILURE 1896 MS14 MSR STEAM SUPPLY VALVE FAILURE 1996 MS21 AUX STM 150 0 HDR CONT VALVE PAILURE 1896 NI04 SR ENERGIZATION AT POWER (P10 PAILURE) 1996 NZ06 PR HL4NNEL UPPER DETECTOR FAILURE 1996 NZ12 AUDIO COUNT RATE CHANNEL FAILURE 1996 RC01 RCS COLD LEG LOOP RUPTURE 1996 RC05 REACTOR VESSEL HEAD FLANGE LEAK

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Attachment to AEP: NRC: 1134A Page 31 COOK NUCLEAR PLANT SIMULATOR MAL1?UNCTION TEST SCHEDULE YEAR 1996 RC09 REACTOR COOLANT PUMP TRIP 1996 RC15 PRESSURIZER SPRAY VALVE FAILURE 1996 RC21 PRT RUPTURE DISC PAILURE 1996 RC26 FAILED FUEL ELEMENT 1996 RD02 BROKEN CONTROL ROD 1996 RD06 UNCONT ROD BANK CONTINUOUS WITHDRAWAL 1996 RD10 CR MOVE OPPOSITE TO DEMAND SIGNAL 1996 RD14 IMPROPER BANK OVERLAP 1996 RD16 ROD CONTROL MG SET TRIP 1896 RH04 RHR HX FLOW CONTROL VALVE FAILURE 1896 RH06 RWST SUPPLY LINE TO RHR PUMP RUPTURE 1996 RH13 SI ACC TANK CHECK VAIVE LEAKAGE 1996 RM02 PROCESS RADIATION MONITOR PAILURE 1996 RP06 SPURIOUS STEAM LINE ISOLATION 1996 RP10 FAILURE OF SI TO ACTUATE-AUTOMATIC 1896 FAILURE OP CZ PHASE h TO MANUAL ACT 1986 RP16 SPURIOUS ACTUATION OF CI PHASE B 1996 RX02 RCS HOT LEG TEMP TRANS FAILURE (NR) 1986 RX06 PZR CAL LEVEL TRANSMITTER FAILURE 1896 RX10 PZR WATER LEVEL CONT OSCILLATION 1896 STEAM DUMP "PRES" CONTROLLER FAILURE 1996 RX16 MS TURB BYPASS HDR PRESS TRANS PAILURE 1986 RX22 SG PROGRQXKD LEVEL SIGNAL FAILURE 1996 RX26 FP TURBINE SPEED CONTROLLER FAILURE 1996 SZ02 SAFETY INJECTION PUMP SHEARED SHAFT 1996 SW03 NESW RUPT ON LWR CONT VENT CLR SUP 1996 SW07 MT OIL TEMPERATURE CONTROLLER FAILURE 1896 TC04 MAIN TURBINE STOP VALVE PAILURE 1996 TC09 MAIN GENERATOR LOAD LIMITER PAII URE 1886 TC13 TURBINE RUNBACK FAILURE 1996 TP05 STATOR COOLING WTR SYS HIGH COND 1886 TU06 TURBINE BLADE EJECTION 1997 CC01 COMPONENT COOLING WATER PUMP TRIP 1997 CC05 MISC CCW HDR RUPTURE IN AUX BUILDING 1997 CC09 CCW LEAK ON RHR PUMP SUPPLY LINE 1997 CC10 CCW LEAKAGE INTO RCP L.BRNG OIL RESERV.

1997 CS02 CONTAIN. SPRAY PUMP. SUCTION BLOCKAGE 1997 CV02 LETDOWN LINE RUPTURE OUTSIDE CONTAIN.

1997 CV06 LETDOWN LINE RELIEF VLV SV-51 LEAKAGE 1997 CV12 CCP FLOW CONTROL VALVE FAILURE 1997 CV16 VCT LEVEL TRANSMITTER FAILURE 1987 CV25 RCP THERMAL BARRIER BX RUPTURE 1997 CV30 REDUCED CCP CAPACITY 1897 CW01 CIRCULATING WATER PUMP TRIP 1997 ED12 LOSS OF 250 VDC POWER (TRAIN h) 1997 ED13 LOSS OF 250 VDC POWER (TRAIN B) 1997 ED23 LOSS OF SWITCHGEAR CONT POWER TRAIN h 1897 ED25 LOSS OF 765/345KV TRANSFORMER BANK I4 1997 EG01 MAIN GENERATOR TRIP 1997 EG06 DIESEL GENERATOR TRIP 1997 EG10 DIESEL GENERATOR FAILURE TO START 1897 EG14 DG RUNNING RELAY FAILURE 1997 FP03 DIESEL GENERATOR ROOM C02 ACTUATZON 1897 FW03 MFW RUPT BETWEEN FEEDFLOW ELMT & FRV

Attachment to AEP: NRC: 1134A Page 32 COOK NUCLEAR PLANT SIMULATOR MALFUNCTION TEST SCHEDULE 1997 FW12 FEEDPUMP TURBINE LUBE OIL SYSTEM LEAK 1997 FW17 HP HTR t6 LVL CONTROLLER AUTO FAILURE 1997 FW21 HP HTR f5 LVL CONTROLLER AUTO FAILURE 1997 FW25 HOTWELI PUMP TRIP 1897 FW29 LP HTR f3 LVL CONT TRANSMITTER FAIL 1997 FW33 LP HEATER BYPASS VALVE FAIIURE 1997 FW37 HOTWELL PUMP DISCHARGE PIPING RUPTURE 1997 FW41 HW LEVEL CONTROL TRANSMITTER FAILURE 1997 FW4 5 HEATER DRAIN PUMP ELO VLV FAILS OPEN 1997 IA03 CONTROL AIR COMPRESSOR TRIP 1997 MS02 MAIN STEAM LINE BREAK AT SG EXIT 1997 MS06 STEAM GENERATOR SAFETY VALVE LEAK 1997 MS11 MSR COIL DRAIN TANK LVL CONT VLV FAIL 1997 MS16 STEAM SEAL CONTROLLER FAILURE 1997 NI01 SOURCE RANGE MONITOR FAILURE 1997 NI05 SOURCE RANGE CHANNEL SPIKES 1997 NI09 PR CHANNEL LOWER DETECTOR FAILURE 1997 NI13 SOURCE RANGE INSTRUMENT BLOWN FUSE 1987 RC02 RCS HOT LEG LOOP LEAK 1997 RC06 RCS EMERGENCY VENT LEAKAGE 1997 RC10 RCS COLD LEG LEAK 1997 RC11 REACTOR COOLANT PUMP HIGH VIBRATION 1997 RC12 RCP LOWER BEARING OIL RESERVOIR LEAK 1997 RC16 PRESSURIZER STEAM SPACE MANWAY LEAK 1997 RC23 STEAM GENERATOR TUBE RUPTURE 1997 RC27 RTD BYPASS MANIFOLD FLOW DEGRADATZON 1997 RD03 STUCK CONTROL ROD (TRIPPABLE) 1997 RD07 UNCONT ROD BANK CONTINUOUS INSERTION 1897 RD11 AUTO CONTROL ROD SPEED FAILURE 1897 RD15 IRPI POWER LOSS 1997 RD19 IMPROPER ROD WORTH 1997 RH01 RHR PUMP TRIP 1997 RH05 RHR HEAT EXCHANGER TUBE LEAK 1987 RH09 RHR PUMP SUCTION PIPE RUPTURE 1997 RH14 SZ ACCljMULATOR TANK LEVEL LOSS 1987 RM03 EBERLINE AREA RADIATION MONITOR FAILURES 1997 RP01 REACTOR TRIP ACB AUTO TRIP FAILURE 1997 RP07 FAILURE OP STEAM LINE ISO TO ACTIVATE 1897 RP11 FAILURE OP SZ TO ACTUATE-MANUALLY 1897 RP19 TRAIN "h" K600 RELAY FAILURES 1997 RP21 FAILURE OF FWZ TRIP TO OCCUR 1997 RX03 RCS COLD LEG TEMP TRANS FAILURE (NR) 1997 RX07 REDUCED PRESSURIZER HEATER CAPACITY 1997 RXl1 SG RELIEF VALVE CONTROLLER FAILURE 1997 RX19 TURBINE IMPULSE TRANSMITTER FAILURE 1997 RX23 SG LEVEL TRANSMITTER FAILURE 1997 RX29 FPC-250 TRANSMITTER FAILURE 1997 SI03 HIGH HEAD SZ LINE RUPTURE 1997 SWOT ESSENTIAL SERVICE WATER PUMP TRIP 1997 TC01 MAIN TURBINE TRIP 1997 TC05 MAIN TURBINE CONTROL VALVE FAILURE 1997 TC10 MAIN GEN OPERATING DEVICE FAILURE 1997 TP01 TURBINE AUX COOLING PUMP TRIP 1997 WD01 RELEASE OF RADIOACTIVE GAS FRCM GDT

Attachment to AEP: NRC: 113%A Page 33 COOK NUCLEAR PLANT SIMULATOR MALFUNCTION TEST SCHEDULE YEAR 1998 CC02 CCW PUMP FAILURE TO AUTO START 1998 CC06 SEAL WATER HX TUBE LEAK 1998 CHol CONTAIN. PRESS. RELIEF VLV FAILURE 1998 CS03 REFUELING WATER STORAGE TANK LEAK 1998 CVO4 LETDOWN LINE ORIFICE ISO. VLV FAILURE 1998 CV09 LETDOWN TEMPERATURE CONTROL FAILURE 1998 CV13 CHARGING PUMP TRIP 1998 CV17 VOLUME CONTROL TANK LEAKAGE 1998 1998 CV26 CV31 REACTOR COOLhllT PUMP tl SEAL FAILURE BACKPRESSURE CONT VLV FAILURERV-200 1998 CW02 CW PUMP DISCHARGE VALVE FAILURE 1998 ED 02 LOSS OF AUXILIARYTRANSFORMER 1998 ED03 LOSS OF RESERVE AUXILIARYTRANSFORMER 1998 ED06 LOSS OF 600 VAC BUS 1998 ED07 LOSS OF 480 VAC BUS 1998 ED11 LOSS OF 250 VDC BUS 1998 ED15 LOSS OF VITAL INST BUS STATIC SWITCH 1998 ED16 AUXILIARIES AUTO BUS TRANSFER FAILURE 1998 ED19 ELECTRICAL GRID LOAD REJECTION 1998 ED20 ANN PANEL POWER SUPPLY PAILURE 1998 ED24 LOSS OF 250 VDC TRAIN "N" BATTERY 1998 EG03 MG AUTO VOLTAGE REG FAILURE TO MANUAL 1998 EG07 DG SPEED CONTROL FAILURE 1998 EG11 DIESEL GENERATOR FAILURE TO TRIP 1998 EG15 MG SEAL OIL UNIT PIPING RUPTURE 1998 FP05 CONTROL R(XX4 CABLE VAULT PIRE 1998 FW05 MAIN FEEDPUMP TURBINE TRIP 1998 FW18 HP HTR 46 LVL CONTROL VALVE FAILURE 1998 FW22 HP HTR 45 LVL CONTROL VALVE FAILURE 1998 FW26 LP HTR 44 LVL CONT TRANSMITTER PhIL 1998 FW30 LP HTR 43 LVL CONTROL VALVE FAILURE 1998 FW34 CONDENSATE BOOSTER PUMP TRIP 1998 FW38 LOSS OF CONDENSER VACUUM 1998 FW42 CONDENSATE STORAGE TANK LEAK 1998 FW46 AUX FEEDPUMP TRIP 1998 FW50 TDAFW PUMP SPEED CONTROLLER FAILURE 1998 FW54 FDWTR RUPT OUTSIDE CONTAINMENT 1998 FW56 FEED PUMP STEAM SUPPLY CONT PAILURE 1998 MS03 MAIN STM LINE BREAK OUTSIDE CONT 1998 MS08 SG STOP VALVE DRIFTS SHUT 1998 MS 12 MSR DRAIN TK ALT DRAIN LVL CONT FAIL 1998 MS17 STEAM SEAL CONTROLLER OSCILLATION 1998 NI02 SOURCE RANGE HV FAILURE TO DEENERGIZE 1998 NI06 INTERMEDIATE RANGE MONITOR PAILURE 1998 NI10 POWER RANGE CHANNEL FAILURE 1998 NI14 INTERMEDIATE RANGE CllhNNEL BLOWN FllSE 1998 RC03 RCS LEAK 1998 RC07 REACTOR COOLANT PUMP LOCKED ROTOR 1998 RC13 RCP UPPER BEARING OIL RESERVOIR LEAK 1998 RC17 FRESSURIZER PORV FAILURE 1998 RC24 STEAM GENERATOR TUBE LEAK 1998 RC28 PRESSURIZER INSTRUMENT LINE LEAKAGE 1998 RD04 STUCK CONTROL ROD (UNTRIPPABLE) 1998 RD08 IN-HOLD-OUT SWITCH FAILURE

ie Attachment to AEP:NRC:1134A Page 34 COOK NUCLEAR PLANT SIMULATOR MALFUNCTION TEST SCHEDULE 1998 RD12 FAILURE OF CONTROL RODS TO MOVE 1998 RD16 IRPZ FAILURE 1998 RH02 RHR PUMP SEAL FAILURE 1998 RH06 RHR INJ HDR RELIEF VALVE PhIL (SV-104) 1998 RH11 RHR RET FLOW TRANS FAILURE (ZPI-335) 1998 RH15 SI ACCUMULATOR N2 PRESSURE LOSS 1998 RP03 FAILURE OP REACTOR TRIP BREAKER 1998 RP08 SPURIOUS FEEDWATER ISOLATION TRIP 1998 RP12 SPURIOUS ACTUATION OF SZ 1998 RP16 FAILURE OP CI PHASE B TO AUTO ACTUATE 1998 RP20 TRAIN "B" K600 RELAY FAILURES 1998 RX04 PRESSURZZER PRESSURE TRANS FAILURE 1998 RX08 PZR SPRAY VALVE AUTO CONTROL FAILURE 1998 RX12 MS RELIEF VLV CONTROLLER OSCIL1ATION 1998 RX16 STEAM DUMP "PRES CONT" ERRATIC OPS 1998 RX20 SG STEAM FLOW TRANSMITTER PAILURE 1998 RX24 FW CONTROL VALVE CONTROLLER PAILURE 1998 RX27 PEED PUMP DP CONTROLLER PAILURE 1998 RX28 LOSS OP 480V lid 1998 SW01 NON ESSENTIAL SERVICE WATER PUMP TRIP 1998 SW05 ESW PIPING RUPTURE 1998 TC02 MAIN TURBINE FAILURE TO TRIP 1998 TC06 MAIN TURBINE ERRATIC CONTROL VALVE 1998 TC11 AUTO LOAD SET OSCILLATION 1998 TP02 TURBINE AUX COOLING PIPING RUPTURE 1998 TU03 MAIN TURBINE HIGH VIBRATION

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